Final safety evaluation report related to certification of the AP1000 standard design : docket no. 52-006. Supplement 1.

Circumferential cracking in the stainless steel pressurized heater sleeves of pressurized water reactors.
Published: (2006)

Final report of NRC AP600 research conducted at Oregon State University /
Published: (1999)

Guidebook to light water reactor safety analysis /
Published: (1985)

Resolution of generic issue 70, "Power-operated relief valve and block valve reliability," and generic issue 94, "Additional low-temperature overpressure protection for light-water reactors," pursuant to 10 CFR 50.54(f).
Published: (1990)

Water coolant technology of power reactors /
by: Cohen, P. (Paul)
Published: (1980)

Water coolant technology of power reactors.
by: Cohen, P. (Paul)
Published: (1969)

Technical resolution of Generic Issue No. B-59-(N-1) loop operation in BWRs and PWRs.
Published: (1986)

2D/3D Program work summary report /
Published: (1993)

Review of LOFT large break experiments : OCED LOFT project /
by: Modro, S. M.
Published: (1989)

Experimental measurement of suppression pool void distribution during blowdown in support of Generic Issue 193 /
by: Ishii, M.
Published: (2014)

Post-test analysis of Hot Leg 2x25% break at PSB-VVER facility using TRACE V5.0 code /
by: Heralecky, P.
Published: (2011)

Coolant Chemistry Control and Effects on Fuel Reliability in Pressurized Heavy Water Reactors Report of a Technical Meeting.
by: IAEA
Published: (2021)

Systems summary of a Westinghouse pressurized water reactor nuclear power plant /
by: Masche, George
Published: (1971)

Supercritcal-water-cooled reactor [SCWR].
Published: (2007)

Investigations of the VVER-1000 Coolant Transient Benchmark Phase 1 with the coupled code system RELAP5/PARCS /
Published: (2009)

Reactor cavity annulus seal ring.
Published: (1978)

Potential impact of debris blockage on emergency recirculation during design basis accidents at pressurized-water reactors.
Published: (2004)

New information regarding insulation material performance and debris blockage of PWR containment sumps.
Published: (1990)

Inaccurate reactor water level indication and inadvertent draindown during shutdown.
Published: (1996)

Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS.
Published: (1982)

Pressurized Heavy Water Reactors : CANDU /
Published: (2022)

Pressurized Heavy Water Reactors : Atucha II /
Published: (2022)

Analysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5/MOD2 /
by: Dillistone, M. J.
Published: (1992)

RELAP5/MOD2 analysis of LOFT experiment L9-4 /
by: Keevill, M. B.
Published: (1992)

Assessment study of RELAP5/MOD2, CYCLE 36.04 based on spray start-up test for DOEL-4 /
by: Moeyaert, P., et al.
Published: (1989)

Potential for loss of emergency cooling function due to a combination of operational and post-LOCA debris in containment.
Published: (1993)

Nuclear steam supply systems ; performance test codes.
Published: (1969)

Auxiliary feedwater sparger and pipe hanger damage.
Published: (1984)

Reliance on water level instrumentation with a common reference leg.
Published: (1984)

Pressure boundary leakage identified on steam generator bowl drain welds.
Published: (2005)

Water cooled reactor safety : an assessment prepared for the Committee on Reactor Safety Technology.
Published: (1970)

Assessment of RELAP5/MOD2 cycle 36.04 with LOFT large break LOCE L2-3 /
by: Bang, Y. S. (Young Seok), et al.
Published: (1992)

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data /
by: Odar, Fuat
Published: (2001)

Development, implementation, and assessment of specific closure laws for inverted-annular film-boiling in a two-fluid model /
by: Cachard, François de
Published: (1996)

Assessment of BETHSY test 9.1.b using RELAP5/MOD3 /
by: Lee, S. (Sukho), et al.
Published: (1993)

Modeling of reactor components using FIDAP : a finite element computer code /
by: Gangadharan, Anand, 1963-
Published: (1989)